Wesley Williams Group Leader, Advanced Reactor Systems Group, Nuclear Energy and Fuel Cycle Division Contact WILLIAMSWC@ORNL.GOV All Publications Capacity Expansion Analysis of Small Modular Reactors Microreactor Simulation Performance Analysis for Real-Time Hardware-in-the-Loop Testbed... A Digital Twin Framework for Liquid-cooled Supercomputers as Demonstrated at Exascale Spallation Neutron Source Hydrogen Relief Analysis for the Cryogenic Moderator System Thermo-Fluid Modeling Framework for Supercomputer Digital Twins: Part 1, Demonstration at Exascale Behavior of contaminants and simulant fission products in the advanced chlorination process Security by Design Business Case Development Semi-empirical model for Henry’s law constant of noble gases in molten salts Machine Learning for Time-Series Prediction of the Cryogenic Moderator System in Oak Ridge National Laboratory's Spallation Neutron Source Facility Space Nuclear Power Autonomous Control Algorithm and Control Element Test Bed Scaled up Process Report – Apparatus and Model Dynamic Modeling of Nuclear Thermal Propulsion Systems Under Drum Fault Conditions Non-Nuclear Advanced Controls Testbed... Knowledge-Informed Uncertainty-Aware Machine Learning for Time Series Forecasting of Dynamical Engineered Systems Development of Microreactor Automated Control System (MACS): Surrogate Plant-level Modeling and Control Algorithms Integration Digital Twin Development of FASTR Frequency Response Analysis of the Molten Salt Demonstration Reactor Dynamic Simulation Model in Transient Simulation Framework of Reconfigurable Models (TRANSFORM) Engineering Scale Simulation of Ortho- Para Hydrogen Conversion Using Hydrogen Analysis Runtime Environment (Hare) in the MOOSE Framework HIGH-LOW FIDELITY THERMAL HYDRAULIC COUPLING USING AI/MACHINE LEARNING ALGORITHMS Uncertainty Quantification in High-Low Dynamic System Coupling using RAVEN and TRANSFORM Building Initial Dynamic System Models for Digital Twins of the Cryogenic Moderator System at the ORNL Spallation Neutron Source Uncertainty Quantification in High-Low Dynamic System Coupling Using RAVEN and TRANSFORM Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Advanced Reactor Systems Group
Research Highlight Adaptive Single Parameter Total Variation Regularization for Derivative Estimation
